GB852151A - Separation of plutonium - Google Patents

Separation of plutonium

Info

Publication number
GB852151A
GB852151A GB1108046A GB1108046A GB852151A GB 852151 A GB852151 A GB 852151A GB 1108046 A GB1108046 A GB 1108046A GB 1108046 A GB1108046 A GB 1108046A GB 852151 A GB852151 A GB 852151A
Authority
GB
United Kingdom
Prior art keywords
solution
plutonium
separation
acid
april
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired
Application number
GB1108046A
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Publication of GB852151A publication Critical patent/GB852151A/en
Expired legal-status Critical Current

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G56/00—Compounds of transuranic elements
    • C01G56/004—Compounds of plutonium
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/42—Reprocessing of irradiated fuel
    • G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/46—Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00—Technologies for solid waste management
    • Y02W30/50—Reuse, recycling or recovery technologies

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Organic Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Chemistry (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

852,151. Separation of plutonium. OLSON, C. M. April 10, 1946 [April 4, 1945], No. 11080/46. Class 39(4). In a process for the separation of plutonium from a nitric acid solution of neutron-irradiated uranium, sufficient formic acid is added to the solution to reduce the plutonium and destroy excess nitric acid, before separating the plutonium. Sulphuric acid or phosphoric acid may also be added to the solution. Preferably the temperature of the solution is 75-90‹C. The concentration of uranyl nitrate in the solution may be from 20 to 70 %, more formic acid being required when the solution is less concentrated. Plutonium may be separated either (a) by adsorption on columbric oxide or on formaldehyde-sulphonated phenol resin, followed by elution with sodium bisulphate solution or (b) by precipitation with bismuth phosphate as carrier as described in Specification 798,685.
GB1108046A 1945-04-04 1946-04-10 Separation of plutonium Expired GB852151A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US852151XA 1945-04-04 1945-04-04

Publications (1)

Publication Number Publication Date
GB852151A true GB852151A (en) 1960-10-26

Family

ID=22190215

Family Applications (1)

Application Number Title Priority Date Filing Date
GB1108046A Expired GB852151A (en) 1945-04-04 1946-04-10 Separation of plutonium

Country Status (1)

Country Link
GB (1) GB852151A (en)

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